Transport equation with delayed neutrons

DOI10.1080/00411459008214507zbMath0711.65119OpenAlexW2035535659MaRDI QIDQ3495614

Gen-Shun Chen

Publication date: 1990

Published in: Transport Theory and Statistical Physics (Search for Journal in Brave)

Full work available at URL: https://doi.org/10.1080/00411459008214507

zbMATH Keywords

monotone sequencesdecayiterative methodtransport equationslab geometrydelayed neutronsnuclear fission reactorupper, lower solutions

Mathematics Subject Classification ID

Numerical methods for integral equations (65R20) Integro-partial differential equations (45K05) Transport processes in time-dependent statistical mechanics (82C70) Nuclear reactor theory; neutron transport (82D75)

Related Items (2)

Spectral analysis of monoenergetic transport equation with delayed neutrons in slab geometry ⋮ Some fixed point theorems in Banach spaces and application to a transport equation with delayed neutrons

Cites Work

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• Subcriticality for transport of multiplying particles in a slab
• Positive Solutions for Reactor Multigroup Neutron Transport Systems: Criticality Problem
• Existence and Uniqueness Theorems for the Neutron Transport Equation

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